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STANDARDS, INTERNATIONAL & INDUSTRY |
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AMERICAN NUCLEAR SOCIETY
American Nuclear Society (ANS) Standards collection covers topics such as: Design criteria for nuclear
power stations, criticality control of fuel mixtures, radioactive dosage
criteria, concrete radiation shields, accident alarm systems for nuclear plants,
safety guide for the performance of critical experiments, determining design
basis flooding at power reactor sites, evaluation of surface water supplies for
nuclear power sites, selection qualification and training of personnel for
nuclear power plants, etc.
ABOUT ANS
The American Nuclear Society is a not-for-profit, international, scientific
and educational organization. It was established by a group of individuals who
recognized the need to unify the professional activities within the diverse
fields of nuclear science and technology. December 11, 1954, marks the Society's
historic beginning at the National Academy of Sciences in Washington, D.C. ANS
has since developed a multifarious membership composed of approximately 10,500
engineers, scientists, administrators, and educators representing 1,600 plus
corporations, educational institutions, and government agencies. It is governed
by three officers and a board of directors elected by the membership.
Mission: The American Nuclear Society serves its members in their efforts to
develop and safely apply nuclear science and technology for public benefit
through knowledge exchange, professional development, and enhanced public
understanding.
AMERICAN NUCLEAR SOCIETY
standards titles, document titles, document numbers,
subject abstracts
ANS 1
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CONDUCT OF CRITICAL EXPERIMENT
ANS 10.2
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PORTABILITY OF SCIENTIFIC AND ENGINEERING SOFTWARE
ANS 10.4
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GUIDELINES FOR THE VERIFICATION AND VALIDATION OF
SCIENTIFIC AND ENGINEERING COMPUTER PROGRAMS FOR THE NUCLEAR
INDUSTRY
ANS 14.1
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OPERATION OF FAST PULSE REACTORS
ANS 15.10
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DECOMMISSIONING OF RESEARCH REACTORS
ANS 15.11
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RADIATION PROTECTION AT RESEARCH REACTOR FACILITIES
ANS 15.16
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EMERGENCY PLANNING FOR RESEARCH REACTORS
ANS 15.17
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FIRE PROTECTION PROGRAM CRITERIA FOR RESEARCH REACH
ANS 15.2
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QUALITY CONTROL FOR PLATE-TYPE URANIUM ALUMINUM FUEL
ELEMENTS
ANS 15.21
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FORMAT AND CONTENT FOR SAFETY ANALYSIS REPORTS FOR
RESEARCH REACTORS
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